Mostra el registre d'ítem simple

dc.contributor.authorAbbondanno, U.
dc.contributor.authorAerts, G.
dc.contributor.authorÁlvarez, F.
dc.contributor.authorCalviño Tavares, Francisco
dc.contributor.authorCortés Rossell, Guillem Pere
dc.contributor.authorPretel Sánchez, Carme
dc.contributor.otherUniversitat Politècnica de Catalunya. Departament de Física
dc.date.accessioned2019-05-31T09:33:01Z
dc.date.available2019-05-31T09:33:01Z
dc.date.issued2003-10-10
dc.identifier.citationAbbondanno, U. [et al.]. "Measurement of the neutron capture cross sections of 233U, 237Np, 240,242Pu, 241,243Am and 245Cm with a Total Absorption Calorimeter at n_TOF". 2003.
dc.identifier.urihttp://hdl.handle.net/2117/133760
dc.descriptionProposal: Measurement of the neutron capture cross sections of 233U, 237Np, 240,242Pu, 241,243Am and 245Cm with a Total Absorption Calorimeter at n_TOF
dc.description.abstractAccurate and reliable neutron capture cross section data for actinides are necessary for the proper design, safety regulation and precise performance assessment of transmutation devices such as Fast Critical Reactors or Accelerator Driven Systems (ADS). The goal of this proposal is the measurement of the neutron capture cross sections of 233U, 237Np, 240,242Pu, 241,243Am and 245Cm at n_TOF with an accuracy of 5%. 233U plays an essential role in the Th fuel cycle, which has been proposed as a safer and cleaner alternative to the U fuel cycle. The capture cross sections of 237Np, 240,242Pu, 241,243Am and 245Cm play a key role in the design and optimization of a strategy for the Nuclear Waste Transmutation. A high accuracy can be achieved at n_TOF in such measurements due to a combination of features unique in the world: high instantaneous neutron fluence and excellent energy resolution of the facility, innovative Data Acquisition System based on flash ADCs and the use of a high performance Total Absorption Calorimeter as a detection device.
dc.format.extent61 p.
dc.language.isoeng
dc.rightsAttribution-NonCommercial-NoDerivs 3.0 Spain
dc.rights.urihttp://creativecommons.org/licenses/by-nc-nd/3.0/es/
dc.subjectÀrees temàtiques de la UPC::Física
dc.subjectÀrees temàtiques de la UPC::Energies::Energia nuclear
dc.subject.lcshNeutrons--Capture
dc.subject.lcshNuclear physics
dc.subject.othern_TOF
dc.subject.otherCERN
dc.subject.otherNeutrons
dc.subject.otherNuclear reaction
dc.subject.otherCross section
dc.subject.otherAccelerator Driven Systems
dc.subject.otherADS
dc.subject.otherAdvanced nuclear reactor
dc.titleMeasurement of the neutron capture cross sections of 233U, 237Np, 240,242Pu, 241,243Am and 245Cm with a total absorption calorimeter at n_TOF
dc.typeExternal research report
dc.subject.lemacNeutrons--Captura
dc.subject.lemacFísica nuclear
dc.contributor.groupUniversitat Politècnica de Catalunya. ANT - Advanced Nuclear Technologies Research Group
dc.relation.publisherversionhttp://cds.cern.ch/record/678357/files/intc-2003-036.pdf
dc.rights.accessOpen Access
local.identifier.drac25151951
dc.description.versionPostprint (published version)
local.citation.authorAbbondanno, U.; Aerts, G.; Álvarez, F.; Calviño, F.; Cortes, G.; Pretel, C.


Fitxers d'aquest items

Thumbnail

Aquest ítem apareix a les col·leccions següents

Mostra el registre d'ítem simple